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NUCLEAR
CHEMICAL
ENGINEERING
Second Edition
Manson Benedict
Professor Emeritus of
Nuclear
Engineering
Massachusetts Institute of Technology
Thomas
H.
Pigford
Professor
of
Nuclear Engineering
University
of
Gal$omia,
Berkeley
Hans Wolfgang Levi
Hahn-Meitner-Institut
fir
Kernforschung Berlin
and
apL
Professor
of
Nuclear Chemistty
Technische Universitat Berlin
McGraw-Hill
Book
Company
New
York
St.
Louis
San
Francisco Auckland
Bogota
Hamburg
Johannesburg London Madrid Mexico Montreal New Delhi
Panama Paris SHoPaulo
Singapore
Sydney Tokyo
Toronto
This
book was set in Press Roman by Hemisphere Publishing Corporation.
The
editor was Diane
D.
Heiberg;
the production supervisor was Rosann
E.
Raspini.
Kingsport Press, Inc.
was
printer and binder.
NUCLEAR CHEMICALENGINEERING
Copyright
0
1981, 1957 by McCraw-Hill, Inc.
All
rights reserved.
Printed in the United States of America. No part
of
this publication
may
be
reproduced, stored in a retrieval system,
or
transmitted, in any
form
or
by any means, electronic, mechanical, photocopying, recording,
or
otherwise, without the prior written permission
of
the publisher.
5
6
7
8
9
0
KPKP
8
9
8
7
6
5
4
Library
of
Congress
Cataloging
in Publication Data
Benedict, Manson
Nuclear chemical engineering,
(McGraw-Hill series in nuclear engineering)
Includes bibliographies and index.
1. Nuclear engineering. 2. Nuclear chemistry.
I.
Pigford, Thomas
H.,
joint author.
11.
Levi,
Hans
Wolfgang, joint author.
111.
Title.
TK9350.B4 1981 621.48 80-21538
ISBN
0-07-004531-3
PREFACE
The development of nuclear fssion chain reactors for the conversion of mass to energy and the
transmutation of elements has brought into industrial prominence chemical substances and
chemical engineering processes that a few years ago were
no
more than scientific curiosities.
Uranium, formerly used mainly for coloring
glass
and ceramics, has become one of the world’s
most important sources of energy. Thorium, once used mainly in the Welsbach
gas
mantle,
promises to become a nuclear fuel second in importance only to uranium. Zirconium and its
chemical twin hafnium, formerly always produced together, have been separated and have emerged
as structural materials of unique value in reactors. New chemicalengineering processes have been
devised to separate these elements, and even more novel processes have been developed for
producing deuterium,
*’’
U,
and the other separated isotopes that have become the fine chemicals
of the nuclear age. The processing of radioactive materials, formerly limited mainly to a few curies
of radium,
is
now concerned with the
millions
of curies of radioactive isotopes of the many
chemical elements that are present in spent fuel discharged from nuclear reactors.
The preceding introduction to the preface of the first edition of this book can still serve as the
theme of this second edition. Since
1957
nuclear power systems have become important
contributors to the energy supply of most industrialized nations.
This
text describes the materials
of special importance in nuclear reactors and the processes that have been developed to
concentrate, purify, separate, and store safely these materials. Because of the growth in nuclear
technology since the first edition appeared and the great amount of published new information,
this second edition is an entirely new book,.following the
first
edition only in its general outline.
Chapter
1
lists the special materials of importance in nuclear technology and outlines the
relationship between nuclear reactors and the chemical production plants associated with them.
Chapter
2
summarizes the aspects of nuclear physics and radioactivity that are pertinent to many
of the processes to be described in later chapters. Chapter
3
describes the changes
in
composition
and reactivity that occur during irradiation of fuel in a nuclear reactor and shows how these
changes determine the material and processing requirements of the reactor’s fuel cycle. Chapter
4
describes the principles of solvent extraction, the chemicalengineering unit operation used most
extensively for purifying uranium, thorium, and zirconium and reprocessing irradiated fuel
discharged from reactors.
Chapters
5,
6,
and
7
take up uranium, thorium, and
zirconium
in that order. Each chapter
discusses
the physical and chemical properties
of
the element and
its
compounds, its natural
occurrence, and the processes
used
to extract the element from its ores, purify it, and convert it
to
the forms most useful
in
nuclear technology.
X
iii
xiv
PREFACE
The next four chapters take up processing of the
highly
radioactive materials produced in
reactors. Chapter
8
describes the isotopic composition and radioactive constituents of spent fuel
discharged from representative types of reactors and deals briefly with other radioisotopes
resulting from reactor operation. Chapter
9
describes the physical and chemical properties of the
synthetic actinide elements produced in reactors: protactinium, neptunium, plutonium,
americium, and curium, and their compounds. Chapter
10
describes the radiochemical processes
that have been developed for reprocessing irradiated fuel to recover uranium, plutonium, and other
valuable actinides from
it.
Chapter
11
describes conversion of radioactive wastes from reactor
operation and fuel reprocessing into stable forms suitable for safe, long-term storage, and systems
to be used
for
such storage.
The
last
three chapters deal with separation of stable isotopes. Chapter
12
lists the isotopes of
principal importance in nuclear technology, discusses their natural occurrence, and develops the
chemical engineering principles generally applicable to isotope separation processes. Chapter
13
describes processes useful for separating deuterium and isotopes of other light elements, specifically
distillation, electrolysis, and chemical exchange. Chapter
14
describes processes used for separating
uranium isotopes, specifically
gaseous
diffusion, the
gas
centrifuge, aerodynamic processes,
mass
and thermal diffusion, and laser-based processes.
Four appendixes list fundamental physical constants, conversion tables, nuclide properties,
and radioactivity concentration limits for nuclear plant effluents.
As may be seen from this synopsis,
this
text combines an account of scientific and engineering
principles
with
a description of materials and processes of importance in nuclearchemical
technology. It aims thus to serve both as
a
text for classroom instruction and as
a
source of
information on chemicalengineering practice in nuclear industry.
Problems at the end of each chapter may prove useful when the text is used for instruction.
References are provided for readers who wish more details about the topics treated in each
chapter. Extensive use has been made of information from the
Roceedings
of the four
International Conferences
on
the Peaceful Uses of Atomic Energy in Geneva, Switzerland,
sponsored by the United Nations, which are listed as
PIG,
followed by the number of the
conference, in the references at the ends of chapters.
This book was written in a transition period when U.S. engineering and business practice was
changing from English to
SI
units. When the references cited used Enash units, these have been
retained in the text in most cases. Equivalent
SI
values are also provided in many passages, or
conversion factors are given in footnotes.
In
addition, conversion tables are provided in App.
B.
The multiplicity of units is regrettable, but it is unavoidable until the world’s technical literature
has changed over completely to the
SI
system.
In
preparing
this
text the authors have been blessed with assistance from
so
many sources that
not all
can
be mentioned here. We are grateful to our respective institutions, Massachusetts
Institute of Technology, University of California (Berkeley), and Hahn-Meitner-Institut (Berlin),
for the freedom and opportunity to write
this
book. For help with calculations, illustrations, and
typing,
thanks
are due Marjorie Benedict, Ellen
Mandigo,
Mary
BOSCO,
Sue
Thur,
and many others.
Editorial assistance from Judith
B.
Gandy and Lynne Lackenbach is acknowledged with gratitude.
To the many generations of students who used the notes
on
which this book is based and helped
to correct
its
mistakes we are greatly indebted. Among our more recent students we
wish
to
thank
Men Croff, Charles Forsberg,
Saeed
Tajik,
and
Cheh-Suei Yang.
Among
our
American professional colleagues we are greatly indebted to Don Ferguson and
his
associates at Oak Ridge National Laboratory;
Paul
McMurray and others of Exxon Nuclear
Company; James Buckham and Wesley Murbach of Allied General Nuclear Services; James
Duckworth of Nuclear Fuel Services, Inc.; Joseph Megy of Teledyne
Wah
Chang Albany Company;
Paul Vanstrum and Edward Von Halle of Union Carbide Corporation; Lombard
Squires,
John
PREFACE
xv
Proctor, and their associates of
E.
I.
duPont de Nemours and Company; Marvin Miller of
MIT;
and
Donald Olander
of
the University of California (Berkeley). In Germany, we
wish
to
thank Hubert
Eschrich of Eurochemic, Richard Kroebel of Kernforschungszentrum Karlsruhe, Erich Merz of
Kernforschungsanlage Jiilich, Walther Schuller of
Wiederaufarbeitungsanlage
Karlsruhe,
and
Eckhart Ewest of Deutsche Gesellschaft fur Wiederaufarbeitung von Kernbrennstoff.
Assistance provided to one of the authors
(MB)
by a fellowship from the Guggenheim
Foundation
is
acknowledged with gratitude.
Despite the valued assistance the authors have had in preparing this text, it doubtless
still
contains many errors and omissions. We shall be grateful to our readers for calling these to
our
attention.
Manson
Benedict
Thomas
H.
pisford
Hans Wolfgang
Levi
CONTENTS
Preface
Chapter
1
Chemical Engineering Aspects of Nuclear
Power
Introduction
Nuclear Fission
Nuclear Fuels
Nuclear Reactor Types
Fuel Processing
Flow
Sheets
Fuel-Cycle Operations
Fuel Reprocessing
lsotope Separation
Nuclear Fusion
References
Problems
Chapter
2
Nuclear Reactions
1 Nuclides
2
Radioactivity
3
Decaychains
4
Neutron Reactions
5
The Fission Process
6
7
Growth and Decay of Nuclides with Simultaneous Radioactive
Decay, Neutron Absorption, and Continuous Processing
Derivation
of
the Bateman Equation (2.17) by
Laplace Transforms
Nomenclature
References
Problems
Chapter
3
Fuel Cycles for Nuclear Reactors
1
Nuclear Fuels
2 Effects of Irradiation
on
Nuclear Fuels
3
Fuel
and
Poison
Management
Xiii
1
1
2
5
7
10
15
20
22
23
24
25
26
26
27
35
42
53
63
76
78
80
81
84
84
87
90
.iii
CONTENTS
4
5
6
7
Chapter
4
1
2
3
4
5
6
7
Chapter
5
1
2
3
4
5
6
7
8
9
10
Chapter
6
1
2
3
4
5
6
7
8
9
10
Chapter
7
1
2
Fuel Management
in
a Large Pressurized-Water
Reactor
Fuel-Cycle Costs
Hand
Calculation of Fuel-Cycle Performance
Fuel-Cycle hiaterial
Flow
Sheets
Nomenclature
References
Problems
Solvent Extraction
of
Metals
Applications
Extractable Metal-Organic Complexes
Solvent Extraction Principles
Distribution Coefficients
Solvent Requirements
Theory of Countercurrent Equilibrium Extraction
Solvent Extraction Equipment
Nomenclature
References
Problems
Uranium
Uranium Isotopes
Uranium Radioactive Decay Series
Metallic Uranium
Uranium Compounds
Uranium Solution Chemistry
Sources of Uranium
Uranium Resource Estimates
Concentration of Uranium
Uranium Refining
Production
of
Uranium Metal
References
Problems
Thorium
Uses of Thorium
Thorium isotopes
Thorium Radioactivity
Metallic Thorium
Thorium Compounds
Thorium Solution Chemistry
Thorium Resources
Concentration and Extraction of Thorium
Purification of Thorium
Conversion of Thorium Nitrate to Oxide, Fluoride,
Chloride,
or
Metal
References
Problems
Zirconium and Hafnium
Uses of Zirconium and Hafnium
Natural Occurrence
105
113
126
144
151
153
154
157
157
157
160
165
172
173
198
21 1
212
214
216
21 6
217
222
223
229
232
234
236
266
274
280
28 1
283
283
283
285
287
289
293
294
298
30 7
309
315
317
318
318
319
CONTENTS
ix
Chapter
8
1
2
3
4
5
Chapter
9
1
2
3
4
5
6
Chapter
10
1
2
3
4
5
6
7
8
Chapter
11
1
2
3
4
5
Production and Rice
Zirconium and Hafnium Metal and
Alloys
Zirconium and Hafnium Compounds
Extraction of Zirconium
and
Hafnium from Zircon
Separation of Zirconium and Hafnium
Production of Metallic Zirconium and Hafnium
Alternatives for Producing Hafnium-Free Zirconium
from Zircon
References
Problems
Properties
of
Irradiated Fuel
and Other Reactor Materials
Fission-Product Radioactivity
Radioactivity of the Actinides
Effect of Fuel-Cycle Alternatives
on
Properties
of Irradiated Fuel
Radioactivity from Neutron Activation
Neutron Activity in Recycled Fuel
Nomenclature
References
Problems
Plutonium and Other Actinide Elements
General Chemical Properties of the Actinides
Properties of Protactinium
Properties
of
Neptunium
Properties of Plutonium
Properties of Americium
Properties
of
Curium
References
Problems
Fuel Reprocessing
Objectives
of
Reprocessing
Composition of Irradiated Fuel
History of Reprocessing
The Purex Process
Reprocessing Thorium-Based Fuels
Reprocessing LMFBR Fuels
Neptunium Recovery in Reprocessing
Prevention
of
Criticality
in
Reprocessing Plants
References
Problems
Radioactive Waste Management
Introduction
High-Level Waste
Non-High-Level Waste
Special Radioactive Waste
Disposal
of Radioactive Waste
319
320
323
330
333
342
348
348
350
352
352
364
381
39
1
401
404
405
406
401
407
420
424
426
449
45
1
454
45 6
457
45 7
45
7
45
8
466
514
527
537
547
556
563
565
565
567
604
609
61
3
x
CONTENTS
6
Chapter
12
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
Chapter
13
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
Assessment of Long-Term Safety
References
Problems
Stable Isotopes: Uses, Separation Methods,
and Separation Principles
Uses
of Stable Isotopes
Isotope Separation Methods
Terminology
Stage Properties
Types of Cascade
The Simple Cascade
The Recycle Cascade
The Ideal Cascade
Close-Separation Cascade
Separative Capacity, Separative Work, and Separation
Potential
Differential Equation for Separation Potential
Equilibrium Time for Isotope Separation Plants
Squared-off Cascade
Generalized Ideal Cascade
Three-Component Isotope Separation
Nomenclature
References
Problems
Separation
of
Isotopes
of
Hydrogen
and Other Light Elements
Sources of Deuterium
Deuterium Production Processes and Plants
Separation Factors
in
Distillation
Distillation of Hydrogen
Distillation of Water
Electrolysis
Electrolysis and Steam-Hydrogen Exchange
Separation Factors
in
Deuterium Exchange Processes
Number of Theoretical Stages
in
Exchange Columns
Monothermal Exchange Processes
Dual-Temperature Water-Hydrogen Sulfide Exchange
Process
Dual-Temperature Ammonia-Hydrogen Exchange Process
Methylamine-Hydrogen Exchange Processes
Dual-Temperature Water-Hydrogen Exchange Processes
Exchange Processes for Separation of Lithium Isotopes
Exchange Processes for Other Elements
Nomenclature
References
Problems
618
624
626
627
627
629
644
647
65 1
65 3
654
65 8
665
667
674
677
684
685
693
70
1
703
70
5
708
708
710
71 2
717
722
738
749
756
760
7 62
767
792
797
799
800
80 1
804
806
808
CONTENTS
xi
Chapter
14
Uranium
Isotope
Separation
Introduction
Isotopic Content of Uranium
Uranium Enrichment Projects
Gaseous
Diffusion
The
Gas
Centrifuge
Aerodynamic Processes
Mass
Diffusion
Thermal Diffusion
Laser Isotope Separation
Nomenclature
References
Problems
Appendixes
A
Fundamental Physical Constants
B
Conversion Factors
C
Properties of the Nuclides
D
Radioactivity Concentration Limits for Selected
Radionuclides
812
812
813
815
818
847
876
895
906
914
922
925
929
933
933
935
937
979
Index
983
[...]... fission reactors As isotope separation processes are of such importance in nuclearchemical engineering, they are discussed briefly in this chapter and in some detail in the last three chapters of this book 1 2 NUCLEARCHEMICALENGINEERING Neutron - ) 1 Flpun 1.1 Fission of 235 Uranium235 nudeus U nucleus by neutron 2 NUCLEAR FISSION The nuclear f w o n process utilized in today's power-producing reactors... B B4 C [C21 IS11 Zircaloy B4 c [E21 CHEMICALENGINEERING ASPECTS OF NUCLEAR WWER 9 Steam Feed Water Pump Primary Water Pump Figure 1.8 Schematic of pressurized-water nuclear power plant is Generotor - Woter Recirculator H 2 0 Coolant Moderator + Condenser Condensote - Feed Water Pump Figure 1.9 Schematic of boiling-water nuclear power plant 10 NUCLEARCHEMICALENGINEERING reactors; helium gas has... encouragement, and patience made this book possible, CHAPTER ONE CHEMICALENGINEERING ASPECTS OF NUCLEAR POWER 1 INTRODUCTION The production of power from controlled nuclear fission of heavy elements is the most important technical application of nuclear reactions at the present time This is so because the world’s reserves of energy in the nuclear fuels uranium and thorium greatly exceed the energy reserves... This chapter gives a brief account of the nuclear fusion reaction and the most important f d l e fuels It continues with a short description of a typical nuclear power plant and outlines the characteristics of the principal reactor types proposed for nuclear power generation It sketches the principal fuel cycles for nuclear power plants and points out the chemicalengineering processes needed to make these... -7520, 29 1-388 1968, especially pp CHEMICAL ENGINEERING ASPECTS OF NUCLEAR POWER 25 B1 Bettis, E S , and R C Robertson: “The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor,” NucL AppL Tech 8:190 (1970) C1 “CANDU-Douglas Point Nuclear Power Station,” NucL Eng 9:289 (1964) C2 Central Electricity Generation Board, London: “Dungeness B AGR Nuclear Power Station,” Report NF-15473,... highest temperature, around 3W°C (572'F), to which it is heated in the reactor The main difference in principle from Fig 1.7 is 8 NUCLEAR CHEMICAL ENGINEERING Steom Coolant Genera tor Steom Condenser Condensote Preheater Feed Woter pump Coolont Circulotor Figure 1.7 Schematic of nuclear power plant with separate fuel, moderator, and coolant that there is no separation of coolant from moderator in the reactor... chemical engineering processes, including isotope separation, separation of metals by solvent extraction, and the separation and purification of intensely radioactive materials on a large scale This text is concerned primarily with methods for producing the special materials used in nuclear fission reactors and with processes for separating isotopes and reclaiming radioactive fuel discharged from nuclear. .. discharged include deterioration of cladding as a result of fuel swelling, thermal stresses or corrosion, and loss of nuclear reactivity Figure 1.16 Gaseous diffusion plant of U.S Department of Energy, Oak Ridge, Tennessee, (Courtesy of US.Atomic Energy Commission.) CHEMICAL ENGINEERING ASPECTS OF NUCLEAR POWER 19 Figure 1.17 Purex plant of U.S Department of Energy, Hanford, Washington (Courtesy of Atlantic... aqueous phase, while uranium remains in the solvent Solvent from contactor I1 is fed to one end of contactor 111, which is stripped at 22 NUCLEAR CHEMICAL ENGINEERING the other end by water, which transfers the uranium to the aqueous phase leaving the contact or After chemical treatment to remove degradation products, the solvent leaving contactor In is reused in contactors I and 11 This brief discussion... SEPARATION Although the isotopes of an element have very similar chemical properties, they behave as completely different substances in nuclear reactions Consequently, the separation of isotopes of certain elements, notably 235U from =U and deuterium from hydrogen, is of great importance in nuclear technology Table 1.5 lists isotopes important in nuclear power applications, together with their natural abundance . Publication Data Benedict, Manson Nuclear chemical engineering, (McGraw-Hill series in nuclear engineering) Includes bibliographies and index. 1. Nuclear engineering. 2. Nuclear chemistry. I. Pigford,. NUCLEAR CHEMICAL ENGINEERING Second Edition Manson Benedict Professor Emeritus of Nuclear Engineering Massachusetts Institute of Technology Thomas H. Pigford Professor of Nuclear. Hans Wolfgang Levi CONTENTS Preface Chapter 1 Chemical Engineering Aspects of Nuclear Power Introduction Nuclear Fission Nuclear Fuels Nuclear Reactor Types Fuel Processing Flow Sheets